Open AccessThe effect of code user and boundary conditions on RELAP calculations of MTR research reactor transient scenarios
Author(s) -
A. Khedr,
Martina Adorni,
Francesco Saverio D'Auria
Publication year - 2005
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp0501016k
Subject(s) - natural circulation , nuclear engineering , transient (computer programming) , boiling water reactor , research reactor , boiling , core (optical fiber) , scram , transient flow , materials science , nuclear reactor , environmental science , flow (mathematics) , mechanics , code (set theory) , computer science , thermodynamics , nuclear physics , steady state (chemistry) , neutron , physics , engineering , chemistry , composite material , set (abstract data type) , programming language , operating system
The safety evaluation of nuclear power and re search reactors is a very important step before their construction and during their operation. This evaluation based on the best estimate calculations requires qualified codes qualified users, and qualified nodalizations. The effect of code users on the RELAP5 results during the analysis of loss of flow transient in MTR research reactors is presented in this pa per. To clarify this effect, two nodalizations for research reactor different in the simulation of the open water surface boundary conditions of the reactor pool have been used. Very different results are obtained with few choices for code users. The core natural circulation flow with the be ginning of core boiling doesn't stop but in creases. The in creasing in the natural circulation flow shifts out the boiling from the core and the clad temperature decreases be low the local saturation temperature